february 6, 2002 6610 nuclear road subject: point ... of changes, tests, or experiments (10 cfr...

February 6, 2002

Mr. M. ReddemannSite Vice PresidentKewaunee and Point Beach Nuclear PlantsNuclear Management Company, LLC6610 Nuclear RoadTwo Rivers, WI 54241

SUBJECT: POINT BEACH NUCLEAR PLANTNRC INSPECTION REPORT 50-266/02-002(DRS); 50-301/02-002(DRS)

Dear Mr. Reddemann:

On January 18, 2002, the NRC completed an inspection at your Point Beach Nuclear Plant. The enclosed report documents the inspection findings which were discussed on January 18,2002, with Mr. Taylor and other members of your staff.

The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission�s rules and regulations and with the conditions of your license. The inspectors reviewed selected procedures and records, observed activities, and interviewedpersonnel. Specifically, this inspection focused on the baseline annual inspection forevaluations of changes, tests, or experiments (10 CFR 50.59) and the baseline biennialinspection for permanent plant modifications.

No findings of significance were identified.

In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC PublicDocument Room or from the Publicly Available Records (PARS) component of NRC'sdocument system (ADAMS). ADAMS is accessible from the NRC Web site athttp://www.nrc.gov/NRC/ADAMS/index.html (the Public Electronic Reading Room).

Sincerely,

/RA/

Ronald N. Gardner, ChiefElectrical Engineering BranchDivision of Reactor Safety

Docket Nos. 50-266; 50-301License Nos. DPR-24; DPR-27

Enclosure: Inspection Report 50-266/02-002(DRS); 50-301/02-002(DRS)

See Attached Distribution

M. Reddemann -2-

cc w/encl: R. Grigg, President and Chief Operating Officer, WEPCoR. Anderson, Executive Vice President and Chief Nuclear OfficerT. Webb, Licensing ManagerD. Weaver, Nuclear Asset ManagerT. Taylor, Plant ManagerA. Cayia, Site DirectorJ. O�Neill, Jr., Shaw, Pittman, Potts & TrowbridgeK. Duveneck, Town Chairman Town of Two CreeksD. Graham, Director Bureau of Field OperationsA. Bie, Chairperson, Wisconsin Public Service CommissionS. Jenkins, Electric Division Wisconsin Public Service CommissionState Liaison Officer

Mr. M. ReddemannSite Vice PresidentKewaunee and Point Beach Nuclear PlantsNuclear Management Company, LLC6610 Nuclear RoadTwo Rivers, WI 54241

SUBJECT: POINT BEACH NUCLEAR PLANTNRC INSPECTION REPORT 50-266/02-002(DRS); 50-301/02-002(DRS)

Dear Mr. Reddemann:

On January 18, 2002, the NRC completed an inspection at your Point Beach Nuclear Plant. The enclosed report documents the inspection findings which were discussed on January 18,2002, with Mr. Taylor and other members of your staff.

The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission�s rules and regulations and with the conditions of your license. The inspectors reviewed selected procedures and records, observed activities, and interviewedpersonnel. Specifically, this inspection focused on the baseline annual inspection forevaluations of changes, tests, or experiments (10 CFR 50.59) and the baseline biennialinspection for permanent plant modifications.


In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC PublicDocument Room or from the Publicly Available Records (PARS) component of NRC'sdocument system (ADAMS). ADAMS is accessible from the NRC Web site athttp://www.nrc.gov/NRC/ADAMS/index.html (the Public Electronic Reading Room).

Sincerely,

/RA/

Ronald N. Gardner, ChiefElectrical Engineering BranchDivision of Reactor Safety

Docket Nos. 50-266; 50-301License Nos. DPR-24; DPR-27

Enclosure: Inspection Report 50-266/02-002(DRS); 50-301/02-002(DRS)

See Attached Distribution

DOCUMENT NAME: C:\Program Files\Adobe\Acrobat 4.0\PDF Output\Poi020602drs.wpdTo receive a copy of this document, indicate in the box: "C" = Copy without attachment/enclosure "E" = Copy with attachment/enclosure "N" = No copy

OFFICE RIII E RIII RIIINAME GHausman:jb RLanksbury RGardnerDATE 02/05/02 02/06/02 02/06/02

OFFICIAL RECORD COPY

M. Reddemann -2-

cc w/encl: R. Grigg, President and Chief Operating Officer, WEPCoR. Anderson, Executive Vice President and Chief Nuclear OfficerT. Webb, Licensing ManagerD. Weaver, Nuclear Asset ManagerT. Taylor, Plant ManagerA. Cayia, Site DirectorJ. O�Neill, Jr., Shaw, Pittman, Potts & TrowbridgeK. Duveneck, Town Chairman Town of Two CreeksD. Graham, Director Bureau of Field OperationsA. Bie, Chairperson, Wisconsin Public Service CommissionS. Jenkins, Electric Division Wisconsin Public Service CommissionState Liaison Officer

ADAMS Distribution:WDR DFT BAWRidsNrrDipmIipbGEGHBCPGK1C. Ariano (hard copy)DRPIIIDRSIIIPLB1JRK1

U. S. NUCLEAR REGULATORY COMMISSION

REGION III

Docket Nos: 50-266; 50-301License Nos: DPR-24; DPR-27

Report No: 50-266/02-002(DRS); 50-301/02-002(DRS)

Licensee: Nuclear Management Company, LLC

Facility: Point Beach Nuclear Plant

Location: 6610 Nuclear RoadTwo Rivers, WI 54241

Dates: January 14 through 18, 2002

Inspectors: Robert C. Daley, Reactor InspectorGeorge M. Hausman, Senior Reactor Inspector (Lead)Kenneth G. O�Brien, Senior Reactor InspectorDarrell L. Schrum, Reactor Inspector

Observer: Nicholas A. Valos, Reactor Inspector (Trainee)

Approved by: Ronald N. Gardner, ChiefElectrical Engineering BranchDivision of Reactor Safety

2

SUMMARY OF FINDINGS

50-266/02-002(DRS); 50-301/02-002(DRS), on 01/14-18/2002, Nuclear ManagementCompany, LLC, Point Beach Nuclear Plant. Evaluations of Changes, Tests, or Experimentsand Permanent Plant Modifications Report.

The report covers a five day announced inspection. The inspection was conducted by fourRegion III based reactor inspectors and one observer in training. No findings of significancewere identified. The significance of most findings is indicated by their color (Green, White,Yellow, Red) using IMC 0609 �Significance Determination Process� (SDP). The NRC�sprogram for overseeing the safe operation of commercial nuclear power reactors is described atits Reactor Oversight Process website at http://www.nrc.gov/NRR/OVERSIGHT/index.html. Findings for which the SDP does not apply are indicated by �No Color� or by the severity level ofthe applicable violations.

A. Inspector Identified Findings

Cornerstones: Initiating Events, Mitigating Systems, Barrier Integrity


3

Report Details

Summary of Plant Status

Units 1 and 2 were operated at or near 100 percent power throughout the inspection period.

1. REACTOR SAFETY

Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity

1R02 Evaluations of Changes, Tests, or Experiments (71111.02)

.1 Review of 10 CFR 50.59 Evaluations and Screenings for Changes, Tests, orExperiments

a. Inspection Scope

The inspectors reviewed ten evaluations performed pursuant to 10 CFR 50.59. Theevaluations related to permanent plant modifications, setpoint changes, procedurechanges, conditions adverse to quality, and changes to the updated final safety analysisreport. The inspectors reviewed the evaluations to verify that the evaluations werethorough and that prior NRC approval was obtained as appropriate. The inspectors alsoreviewed fifteen screenings where the licensee had determined that a 10 CFR 50.59evaluation was not necessary. In regard to the changes reviewed where no 10 CFR50.59 evaluation was performed, the inspectors verified that the changes did not meetthe threshold to require a 10 CFR 50.59 evaluation. These evaluations and screeningswere chosen based on risk significance of samples from the different cornerstones.

b. Findings


1R17 Permanent Plant Modifications (71111.17)

.1 Review of Recent Permanent Plant Modifications

a. Inspection Scope

The inspectors reviewed ten permanent plant modifications that were installed in the lasttwo years. The modifications were chosen based upon their affecting systems that hadhigh probabilistic risk analysis (PRA) significance in the licensee's Individual PlantEvaluation (IPE) or high maintenance rule safety significance. The inspectors reviewedthe modifications to verify that the completed design changes were in accordance withthe specified design requirements and the licensing bases and to confirm that thechanges did not affect any systems' safety function. Design and post-modificationtesting aspects were reviewed to ensure the functionality of the modification, its

4

associated system, and any support systems. The inspectors also reviewed themodifications performed to verify the modification did not place the plant in an increasedrisk configuration.

b. Findings


4. OTHER ACTIVITIES (OA)

4OA2 Identification and Resolution of Problems

a. Inspection Scope

The inspectors reviewed a selected sample of corrective action documents associatedwith the licensee�s permanent plant modifications and concerning 10 CFR 50.59evaluations and screenings to verify that the licensee had an appropriate threshold foridentifying issues. The inspectors evaluated the effectiveness of the corrective actionsfor the identified issues.

b. Findings


4OA6 Meetings

Exit Meeting

The inspectors presented the inspection results to Mr. Taylor and other members oflicensee management at the conclusion of the inspection on January 18, 2002. Thelicensee acknowledged the findings presented. No proprietary information wasidentified.

5

KEY POINTS OF CONTACT

Nuclear Management Company, LLC

J. Anderson, Production Planning ManagerL. Armstrong, Design Engineering ManagerD. Black, Nuclear Safety EngineerD. Carter, Seismic Qualification EngineerA. Cayia, Site Operations DirectorD. Dobson, IST EngineerC. Drescher, Modification EngineerJ. Ertman, NMC Fleet Fire Protection EngF. Flentje, Licensing SpecialistN. Hoefert, Programs Engineering ManagerJ. Hanna, System EngineerR. Hornak, Supervising EngineR. Hannemann, Supervising EngineerD. Hettick, Performance Improvement ManagerK. Holt, Supervising EngineerV. Kaminskas, Maintenance ManagerT. Kendall, Supervising EngineerA. Little, System EngineerJ. Marean, Engineering Drafting SupervisorJ. MacNamara, Supervising EngineerR. Mende, KPB Engineering DirectorD. Pederson, System EngineerL. Peterson, Engineering Processes ManagerK. Peveler, Nuclear Oversight ManagerR. Repshas, KPB Site Services ManagerJ. Roberts, MOV EngineerM. Rosseau, Supervising EngineerD. Schoon, Operations ManagerT. Taylor, Plant ManagerS. Thomas, Radiation Protection ManagerT. Vandenbosch, AOP Coordinator

NRC

P. Krohn, Senior Resident Inspector

6

LIST OF ACRONYMS USED

ADAMS Agencywide Documents Access and Management SystemAFW Auxiliary FeedwaterANSI American National Standards InstituteAOP Abnormal Operating ProcedureATWS Anticipated Transient Without ScramCCW Component Cooling WaterCFR Code of Federal Regulationsdc Direct CurrentDPR Demonstration Power ReactorDRS Division of Reactor SafetyECR Engineering Change RequestEDG Emergency Diesel GeneratorEOP Emergency Operating ProcedureEQ Environmental QualificationESFAS Engineered Safety Features Actuation SystemF FahrenheitFSAR Final Safety Analysis ReportFW FeedwaterGL Generic Lettergov Governmenthtml Hypertext Markup Languagehttp Hypertext Transfer ProtocolHVAC Heating Ventilation and Air ConditioningHX Heat ExchangerIA Instrument AirIMC Inspection Manual ChapterIPE Individual Plant EvaluationIR Inspection ReportIST In-service TestingKPB Kewaunee and Point BeachLLC Limited Liability CompanyLOV Loss of VoltageMCC Motor Control CenterMFW Main FeedwaterMOV Motor Operated ValveNEI Nuclear Energy InstituteNMC Nuclear Management CompanyNRC United States Nuclear Regulatory CommissionNRR Office of Nuclear Reactor RegulationOA Other ActivitiesPARS Publicly Available RecordsPBNP Point Beach Nuclear PlantPRA Probabilistic Risk AnalysisQA Quality AssuranceQC Quality Control

LIST OF ACRONYMS USED

7

RG Regulatory GuideRHR Residual Heat RemovalRPS Reactor Protection SystemRCP Reactor Coolant PumpRCS Reactor Coolant SystemRWST Refueling Water Storage TankSD ShutdownSDP Significance Determination ProcessSE Safety EvaluationSER Safety Evaluation ReportSFP Spent Fuel PoolSI Safety InjectionSSFI Safety Systems Functional InspectionSW Service WaterTDAFW Turbine Driven Auxiliary FeedwaterTRM Technical Requirements ManualTS Technical SpecificationUSAR Updated Safety Analysis ReportUSI Unresolved Safety IssueV VoltWE Wisconsin Electricwpd WordPerfect Documentwww World Wide Web

8

LIST OF DOCUMENTS REVIEWED

The following is a list of licensee documents reviewed during the inspection, includingdocuments prepared by others for the licensee. Inclusion on this list does not imply that NRCinspectors reviewed the documents in their entirety, but rather that selected sections or portionsof the documents were evaluated as part of the overall inspection effort. Inclusion of adocument in this list does not imply NRC acceptance of the document, unless specifically statedin the inspection report.

CALCULATIONSNumber Description Rev/Date

692301-2.2 Effect of Loss of Ventilation on Critical Plant Areas at thePBNP Following a Station Blackout

2

99-0031 Structural Qualification of D-07 and D-08 Seismic Brace 099-0117 Evaluate Temporary 8 Inch SW Discharge from CCW HX 1Bechtel# 6118

Primary Auxiliary Building Ventilation Calculation February 16, 1970

N93-060 WE - PBNP Battery D305 DC System Calculation 1N94-056 SFP HX 013A/B - SW Flow vs Temperature Requirement 2N94-130 4160V and 480V Safeguards Buses LOV Relay Setpoints 1N-94-158 Verification of Required AFW Pump Differential Head for

Accident Flow RateNovember 15, 1994

M-09334.212-AF.1

Turbine Driven AFW Low Pressure Capability July 10, 1997

M-09334.425-AF.1

Evaluation of Impact of Check Valve AF-100/AF-101Replacement

0

WE 0005-10 Determination of Time Available to Isolate the RWST 0WE 300060 Piping System Qualification Report, Service Water Piping 1WE 300068 Piping System Qualification Report - Service Water Piping,

Return from HX-13A and HX-13B0

CONDITION REPORTS (CRs) GENERATED DURING INSPECTIONNumber Description Rev/Date

CAP001871 QA Calculation Cannot Be Found in Controlled Records January 15, 2002CAP001877 FSAR Discrepancy on Definition of RG 1.97 Category 2 January 16, 2002CAP001886 Incomplete 10 CFR 50.59 Screening Answer for Changes

to Relief Valve CC-736A/BJanuary 16, 2002

CAP001897 Letdown Isolation Valve Appendix R Operation DuringDegraded Voltage Conditions

January 17, 2002

CAP001900 Incomplete Corrective Actions Regarding Classification ofRC-427

January 17, 2002

CAP001901 FSAR Chapter 9 Changes for CFC Service Water Pressure Not Also Made in Chapter 6

January 17, 2002

CAP001910 Safety Evaluation 2000-0014 Incomplete January 17, 2002

CONDITION REPORTS (CRs) GENERATED DURING INSPECTIONNumber Description Rev/Date

9

CAP001915 Questioning Corrective Action for CR00-2859 on Screening Procedure Temp Change

January 18, 2002

CAP001916 Incorrect Answer to Tech Spec Change Question in 10 CFR 50.59 Evaluation

January 18, 2002

CAP003518 IT-21/22 Needs Procedural Tie January 16, 2002

CONDITION REPORTS (CRs) GENERATED PRIOR TO INSPECTIONNumber Description Rev/Date

96-1631 Unanticipated Alarm on G-03 During Start June 28, 199797-0174 Incorrect SW System Design Pressure Stated in DG-M-03 January 20, 199797-1089 Momentary Air Bank Pressure Low Alarm Received

When G03 EDG Started for Performance of TS-83April 5, 1997

99-1618 Concern ID�d with SW System Operating Pressure During Design Basis Accident with Only 1 Unit in Operation

September 24, 1999

00-0128 P32 Thermocouple Installation Not Documented January 11, 200000-0204 Inappropriate Use of Pre-Screening Criteria January 20, 200000-1155 Less Than Adequate 10 CFR 50.59's April 7, 200000-2841 Abnormal Operating Procedure 6E Concerns September 22, 200000-2859 Installation of Temporary Gauge for AFW Pump Causes

Potential to Violate Technical SpecificationsSeptember 27, 2000

01-1221 Procedures Incorrectly Exempted from 10 CFR 50.59Screening

April 11, 2001

01-0403 Inadequate Safety Screening February 8, 2001

DRAWINGSNumber Description Rev/Date

EnertechPD99532

Nozzle Check Valve, 3�, Class 600 DRV-Z 3

EMD8413730,Sh. 3

Schematic Diagram Diesel Generator G01 Start No. 1Circuitry

December 11, 2001

EMD8413730,Sh. 4

Schematic Diagram Diesel Generator G01 Start No. 2Circuitry

December 11, 2001

EMD8413730,Sh. 6

Schematic Diagram Diesel Generator G01 AnnunciatorPart-2

November 13, 2001

MFWK00000138

Feed Water System 38

MAFK00000169

Auxiliary Feed Water System 69

ENGINEERING CHANGE REQUESTS (ECRs)Number Description Rev/Date

1999-0186 MR 98-024*B October 26, 1999


10

2000-0016 MR 98-024*B March 16, 20002000-0020 MR 98-024*E March 28, 20002000-0023 MR 98-024*B September 18, 20002000-0024 MR 98-024*B September 14, 20002000-0025 MR 98-024*B September 11, 20002000-0026 MR 98-024*B September 18, 20002000-0030 MR 98-024*E April 4, 20002000-0032 MR 98-024*B September 18, 20002000-0033 MR 98-024*B September 18, 20002000-0034 MR 98-024*E May 30, 20002000-0036 MR 98-024*E August 22, 20002000-0038 MR 98-024*E August 22, 20002000-0039 MR 98-024*E April 11, 20002000-0040 MR 98-024*E May 31, 20002000-0041 MR 98-024*E April 5, 20002000-0042 MR 98-024*E May 3, 20002000-0043 MR 98-024*E April 6, 20002000-0044 MR 98-024*B September 14, 20002000-0046 MR 98-024*E April 7, 20002000-0047 MR 98-024*E April 11, 20002000-0049 MR 98-024*E April 8, 20002000-0050 MR 98-024*E April 10, 20002000-0052 MR 98-024*E April 10, 20002000-0054 MR 98-024*E April 12, 20002000-0056 MR 98-024*E April 26, 20002000-0060 MR 98-024*E April 20, 20002000-0061 MR 98-024*E April 26, 20002000-0063 MR 98-024*E May 23, 20002000-0064 MR 98-024*E April 28, 20002000-0066 MR 98-024*E May 3, 20002000-0078 MR 98-024*E June 1, 20002000-0085 MR 98-024*E June 14, 20002000-0093 MR 98-024*E June 14, 20002000-0094 MR 98-024*E June 14, 20002000-0101 MR 98-024*E June 19, 20002000-0108 MR 98-024*E June 29, 20002000-0109 MR 98-024*E July 4, 20002000-0112 MR 98-024*E July 10, 20002000-0117 MR 98-024*E July 8, 20002000-0128 MR 98-024*B September 18, 20002000-0135 MR 98-024*B September 11, 20002000-0137 MR 98-024*B September 11, 2000


11

2000-0141 MR 98-024*B September 13, 20002000-0156 MR 98-024*E August 11, 20002000-0157 MR 98-024*B October 3, 20002000-0158 MR 98-024*B September 18, 20002000-0161 MR 98-024*B September 18, 20002000-0165 MR 98-024*B September 14, 20002000-0174 MR 98-024*B October 4, 20002000-0204 MR 98-024*E October 26, 20002001-0017 MR 98-024*E February 14, 20012001-0027 MR 98-024*E February 27, 2001

MODIFICATIONS:Number Description Rev/Date

MR 94-048 Seismic Modifications of 1A-05, 2A-05, D-07, and D-08 February 10, 1999MR 97-129*A U1 Replace Check Valves AF-100 and AF-101 With a

New StyleMay 27, 1999

MR 98-024*B U0 Spent Fuel Pool Cooling Service Water Alternate Supply/ Return Lines

April 28, 1999

MR 98-024*E U0 Service Water From Component Cooling Water HeatExchanger Return Header Piping/Isolation

January 10, 2000

MR 98-047 U1 Pressurizer Level Controller Upgrade April 13, 1998MR 99-005*C Instrument Air Containment Isolation Valve Trim Package

ReplacementJune 17, 1999

MR 99-0055 Instrument Air Containment Isolation Valve Logic Change February 17, 2000MR 99-029*A AFW Pump P-38A Minimum Flow Re-circulation Line

OrificeJanuary 28, 2000

MR 00-051 RWST (T-013) Vent Upgrade - Unit 1 June 12, 2000MR 00-070 Elimination of Nuisance Low Starting Air Pressure Alarms

During EDG Start of G01May 21, 2001

PROCEDURESNumber Description Rev/Date

AOP-6E Alternate Boration/Loss of Shutdown Margin 8 & 9AOP-6F Low Concentration Water Pockets in RCS 2AOP-6H Quadrant Power Tilt 0AOP-27 Recovery from Inadvertent Containment Isolation (Unit 2) 0CSP-H.1 U2 Response to Loss of Secondary Heat Sink 22CSP-S.1 Response to Nuclear Power Generator ATWS 22EOP-0.1 Reactor Trip Response - Unit 2 25EOP-1.1 Safety Injection Termination (Unit 2) 28EOP-1.3 Transfer to Containment Sump Re-circulation Unit 2 26

PROCEDURESNumber Description Rev/Date

12

IT-08A Cold Start of TDAFW Pump and Valve Test (Quarterly)Unit 1

25

IT-10 Test of Electrically-Driven AFWPs and Valves (Quarterly) 43IT-10 Temporary Change 2000-0463 39IT-110 Instrument Air Valves (Quarterly) Unit 1 16IT-115 Instrument Air Valves (Quarterly) Unit 2 15IT-305B Steam Generator B Main Feed Line Check Valves

(Cold SD) Unit 27

IT-350 SI Check Valves (Cold Shutdown) 2IWP96-071*A2

EDG G01 Governor Replacement Post-ModificationTesting

0

NP1.1.2 Procedure and Administrative Controls 4NP1.1.3 Procedure Preparation Review and Approval 14NP1.1.4 Use and Adherence of Procedures and Work Plans 6NP5.1.8 10CFR50.59/72.48 Applicability, Screening and Evaluation 1NP7.2.1 Plant Modifications 8NP10.3.1 Authorization of Changes, Tests, and Experiments 14OM3.7 AOP and EOP Procedure Sets Use and Adherence 10ORT47 IA Supply Unit 1 17ORT47 IA Supply Unit 2 14ORT48 IA Supply Unit 1 16ORT48 IA Supply Unit 2 121ICP02.003-A-1

RPS Logic Train A Monthly Surveillance Test 11 & 12

1ICP02.003-B-1

RPS Logic Train B Monthly Surveillance Test 12 & 13

1SOP-CC-001Component Cooling System 6 & 7

REFERENCESNumber Description Rev/Date

EWR 97-159 Determine Replacement Check Valve Design forAF-100/101

December 16, 1997

DBD-02 CCW System Design Basis Document 0DBD-29 Auxiliary Building and Control Building HVAC 0FSAR Chapters 6 and 9 June 2001Letter NRC SER on Resolution of USI A-46 at PBNP July 7, 1998Letter Conformance to RG 1.97 for PBNP July 11, 1986Memo Hannemann to O�Brien, Follow-Up on Plant Walkdown of

PAB Ventilation System,January 17, 2002

2000-026 Manager�s Supervisory Staff Meeting Minutes May 2, 2000NPM 99-0864 Seismic Evaluation of Auxiliary Bldg HVAC System July 29, 1999

REFERENCESNumber Description Rev/Date

13

NPM 99-1099 Downgrading Seismic Classification of FW Regulating &Bypass Valves

September 28,1999

PBF-2031 Auxiliary Building Shift Log 43PBF-2031 Daily Logsheet 56RG 1.97 Instrumentation For Light-Water-Cooled Nuclear Power

Plants To Assess Plant And Environs Conditions During And Following An Accident - Revision 2

December 1, 1980

SPEED2000-131

Set Point, Drawing Number, and Capacity Change forCC-736A Spare Parts Equivalency Document

November 8, 2000

50.59 EVALUATIONS(SEs)Number Description Rev/Date

99-0075-02 Instrument Air Containment Isolation Valve Trim PackReplacement

March 22, 2000

2000-0014 Downgrade the Seismic Design Classification of AuxiliaryBuilding Ventilation and MFW Equipment That Isolates the Supply of MFW to the Steam Generators in FSAR

February 16, 2000

2000-0022-01 Chapter 8, DG Systems FSAR Changes 02000-0023-01 FSAR Phase II Review and Upgrade Project, Section 9.6

SWAugust 30, 2000

2000-0044 Refueling Water Storage Tank (RWST) Seismic Upgrade April 4, 20002000-0052 MR 98-024*V - Modify SI Logic for Non-Essential SW

Load Isolation ValvesMay 3, 2000

2000-0055 AFW Pump P-38A and P-38B Minimum Flow RecirculatingLine Flow Orifice Replacement

May 10, 2000

2000-0063 MR 97-014*E, Transfer dc Supplies for Inverters 1DY-01and 2DY-02, Install Panel D-26 and Transfer Loads to D-26

June 20, 2000

2000-0077 Changes to SW System Operating Procedures and FSAR August 9, 20002000-0093 Revise Procedure for Spurious Operation of SI 851 A/B

ValvesSeptember 21, 2000

2001-0007 CCW System Closed Loop Inside Containment 02001-0014 MR 98-024*J - Unit 1 Containment Fan Cooler and Fan

Motor Cooler ReplacementMarch 14, 2001

2001-0027 MR 00-103, SW Upgrades to EDG, G02 June 6, 20012001-0057 TRM 3.5.1/TSR 3.5.1.3 & TSR 3.5.1.3 Bases

(Draft Rev. C)October 16, 2001

2001-0216 Filling RHR Common Suction From RWST With P-33 April 3, 2001

50.59 SCREENS(SCRs)Number Description Rev/Date

1999-0430 Replace 3" AFW Check Valves 1AF-0100 and 1AF-0101 May 28, 1999

50.59 SCREENS(SCRs)Number Description Rev/Date

14

2000-0023 RMP 9200-6, Switchyard Battery D-800, D-801, and D-807 Capacity Test

0

2000-0062 Changes to PBNP 6/99 FSAR Section 8.6 120Vac VitalInstrument Power (Y)

January 28, 2000

2000-0072 Changes to PBNP June 99 FSAR Section 7.2, RPS, 7.3,ESFAS, and 7.6.1, Nuclear Instrumentation System

February 3, 2000

2000-0100 1-SOP-CC-001, Component Cooling System, Revision 2,2-SOP-CC-001, Component Cooling System, Revision 3,PBF 2031, Auxiliary Building Shift Log, Revision 43

February 9, 2000

2000-0207 Revise TLB-59 (Tank Level Book, Diesel GeneratorG-03/G-04 Day Tank T-176A/B)

March 6, 2000

2000-0401 Temporary Ventilation for Main Feed Pump Motors May 8, 20002000-0695 Replacement Valve and Setpoint Change for Unit 1 & 2

CC-736A/BSeptember 7, 2000

2000-0783 50.59 Screening, AF Vent & Drain Temporary Gauges September 14, 20002000-0975 Relief Valve Capacity Change for Unit 2 CC-736A October 28, 20002001-0053 Temporary Changes to EDG G-03 Temperature and

Alarm FunctionsJanuary 19, 2001

2001-0067 Downgrade CCW Heat Exchanger SW Relief Valves From Safety Related to Augmented Quality

January 31, 2001

2001-0084 Service Water System Malfunction January 26, 20012001-0141 Revise RMP 9367, Containment Coatings to Include

Lenience on Dry Film Thickness Range for Carboguard890

February 16, 2001

2001-0205 AOP 27, Recovery from Inadvertent Containment Isolation

March 6, 2001

2001-0208 ORT 69, Revision 21, CCW To and From 1P-1B Refueling Shutdown Unit 1

March 6, 2001

2001�0216 Filling RHR Common Suction From RWST With P-33 April 3, 2001

LIST OF INFORMATION REQUESTED

15

INITIAL DOCUMENT REQUEST(Sent to Licensee on December 18, 2001)

Inspection Report: 50-266/02-002(DRS); 50-301/02-002(DRS)

Inspection Dates: January 14 -18, 2002

Inspection Procedures: IP 71111.02, �Evaluations of Changes, Tests, or Experiments�IP 71111.17, �Permanent Plant Modifications�

Lead Inspector: George M. Hausman, (630) 829-9743

I. Information Needed for In-Office Preparation Week

The following information is needed by January 7, 2002, or sooner, to facilitate theselection of specific items that will be reviewed during the on-site inspection week. Theteam will select specific items from the information requested below and submit a list toyour staff by January 10, 2002. We request that the specific items selected from thelists be available and ready for review on the first day of inspection. If you have anyquestions regarding this information, please call the team leader as soon as possible. All lists requested should cover a two year span. All information should be sentelectronically (as a PDF or WordPerfect/Word document) if at all possible.

a. List of permanent plant modifications to risk significant systems, structures, orcomponents. For the purpose of this inspection, permanent plant modificationsinclude permanent: (i) plant changes, (ii) design changes, (iii) set point changes,(iv) procedure changes, (v) equivalency evaluations, (vi) suitability analyses,(vii) calculations, and (viii) commercial grade dedications.

b. List of all 10 CFR 50.59 completed evaluations involving: (i) changes to facility(modifications), (ii) procedure revisions, (iii) tests or non-routine operatingconfigurations, (iv) changes to the UFSAR, and (v) calculations.

c. List of all 10 CFR 50.59 screenings for changes that have been screened out asnot requiring a full evaluation involving: (i) changes to facility (modifications),(ii) procedure revisions, (iii) tests or non-routine operating configurations,(iv) changes to the UFSAR, and (v) calculations.

d. List of all 10 CFR 50.59 validations or applicability reviews done in lieu of a full10 CFR 50.59 evaluation.

e. List of corrective action documents (open and closed) that address the plantpermanent modification process and 10 CFR 50.59 issues or concerns.


16

f. List of special tests or experiments and non-routine operating configurations.

g. Copies of modification procedure(s), post-modification testing procedure(s) and10 CFR 50.59 procedures.

h. Name(s) and phone numbers for the regulatory and technical contacts.

i. Latest Organizational Chart.

II. Information to be Available on First Day of Inspection (January 14, 2002)

a. Copies of all selected items need to be ready for the inspectors when they arriveon-site. Selected items will be relayed to the NRC coordinator/contact person byJanuary 10th.

b. The following information needs to be available to the team once they arriveon-site. Copies of these documents do not need to be solely available to theteam as long as the inspectors have easy and unrestrained access to them.

� Updated Final Safety Analysis Report

� Technical Specifications

� Latest IPE/PRA Report

� Vendor Manuals

� The Latest 10 CFR 50.59 FSAR Update Submittal

c. Please ensure that all supporting documents for the selected items have beenlocated and are readily retrievable as the team will likely be requesting thesedocuments during the inspections. Examples of supporting documents are:

� Calculations supporting the selected modifications or 10 CFR 50.59evaluations

� Post-modification tests for the selected modifications

� Copies of other evaluations or validations referred to by a modification or10 CFR 50.59 evaluation.

� Drawings supporting the modifications.

� Procedures affected by the modifications.


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� UFSAR change papers generated due to a 10 CFR 50.59 evaluation.

III. Information to Be Provided Throughout the Inspection

a. Copies of any Condition Report generated as a result of the team�s questions orqueries during this inspection.

b. Copies of the list of questions submitted by the team members and thestatus/resolution of the information requested (provided daily during theinspection to each team member).